ENTRY 14473 20170720 14331447300000001 SUBENT 14473001 20170720 14331447300100001 BIB 13 35 1447300100002 TITLE 181Ta(n,gamma) cross section and average resonance 1447300100003 parameter measurements in the unresolved resonance 1447300100004 region from 24 to 1180 keV using a filtered-beam 1447300100005 technique 1447300100006 AUTHOR (B.J.McDermott,E.Blain,A.Daskalakis,N.Thompson, 1447300100007 A.Youmans,H.J.Choun,W.Steinberger,Y.Danon,D.P.Barry, 1447300100008 R.C.Block,B.E.Epping,G.Leinweber,M.R.Rapp) 1447300100009 INSTITUTE (1USARPI,1USAKAP) 1447300100010 REFERENCE (J,PR/C,96,014607,2017) 1447300100011 #doi:10.1103/PhysRevC.96.014607 1447300100012 FACILITY (LINAC,1USARPI) Experiments were performed at the 1447300100013 Gaerttner Linear Accelerator Laboratory at Rensselaer 1447300100014 Polytechnic Institute using electron linac. 1447300100015 INC-SOURCE (PHOTO) Photoneutrons were produced by 1447300100016 bremsstrahlung X-rays in the Ta target. The LINAC 1447300100017 electron pulse width was set to a nominal value of 30 1447300100018 ns, and the pulse repetition rate was set to 400 Hz. 1447300100019 METHOD (FNB,PHWT,TOF) The filtered-beam runs were performed by1447300100020 placing a 30 cm slab of elemental iron in the path of 1447300100021 the neutron beam. A 5/32 in. thick B4C filter was also 1447300100022 placed in the beam to remove any low-energy overlap 1447300100023 neutrons. 1447300100024 DETECTOR (SCIN) Four deuterated benzene (C6D6) scintillation 1447300100025 detector modules with thin-walled aluminum scintillator1447300100026 cells and light shields, a thin mu-metal tape for 1447300100027 magnetic shielding and boron-free photomultiplier tube 1447300100028 windows 1447300100029 SAMPLE Pure elemental tantalum samples with purity 99.95% 1447300100030 with dimensions 10 x 10 cm2 and thickness of 0.0358 1447300100031 and 0.0112 atm/b. 1447300100032 MONITOR (5-B-10(N,A)3-LI-7,,SIG,G) 1447300100033 478 keV photons measured 1447300100034 MONIT-REF (,A.D.Carlson+,J,NDS,110,3215,2009) 1447300100035 ADD-RES Cross sections from unfiltered neutrons 1447300100036 HISTORY (20170717C) Compiled by S.H. 1447300100037 ENDBIB 35 0 1447300100038 NOCOMMON 0 0 1447300100039 ENDSUBENT 38 0 1447300199999 SUBENT 14473002 20170720 14331447300200001 BIB 6 12 1447300200002 REACTION (73-TA-181(N,G)73-TA-182,,SIG) 1447300200003 STATUS (TABLE) Data taken from tab. 4 of the reference 1447300200004 ANALYSIS Final values are average values of two measurements 1447300200005 with different samples 1447300200006 ERR-ANALYS (DATA-ERR) Total uncertainty. Uncertainty terms are 1447300200007 taken to be the larger of either the internal 1447300200008 statistical uncertainty of the data points or the 1447300200009 external systematic uncertainty between the two 1447300200010 measurements 1447300200011 CORRECTION Corrections for self-shielding and multiple scattering 1447300200012 were made 1447300200013 MISC-COL (MISC) Central point of energy bin 1447300200014 ENDBIB 12 0 1447300200015 NOCOMMON 0 0 1447300200016 DATA 5 17 1447300200017 EN-MIN EN-MAX MISC DATA DATA-ERR 1447300200018 KEV KEV KEV B B 1447300200019 20.999 25.991 23.654 0.937 0.029 1447300200020 79.977 82.697 81.592 0.443 0.016 1447300200021 125.88 129.63 127.82 0.346 0.014 1447300200022 134.51 138.65 136.85 0.340 0.0089 1447300200023 165.94 169.16 167.54 0.312 0.011 1447300200024 180.59 185.48 183.31 0.299 0.011 1447300200025 217.55 220.76 219.14 0.261 0.012 1447300200026 268.22 276.55 272.62 0.242 0.0071 1447300200027 296.95 315.50 308.01 0.224 0.0055 1447300200028 343.57 360.73 351.59 0.205 0.0060 1447300200029 372.00 379.20 375.57 0.190 0.0071 1447300200030 463.10 471.85 466.82 0.181 0.0090 1447300200031 550.12 561.46 554.94 0.186 0.016 1447300200032 619.95 664.18 643.51 0.163 0.0045 1447300200033 688.09 710.96 699.38 0.153 0.0058 1447300200034 929.22 968.97 946.98 0.136 0.0061 1447300200035 1132.6 1227.8 1181.2 0.108 0.0064 1447300200036 ENDDATA 19 0 1447300200037 ENDSUBENT 36 0 1447300299999 SUBENT 14473003 20171129 14331447300300001 BIB 5 9 1447300300002 REACTION (73-TA-181(N,EL),,STF) 1447300300003 STATUS (TABLE) Data taken from tab. 5 of the reference 1447300300004 (DEP,14473002) 1447300300005 ANALYSIS Average resonance parameters were fit to both filtered 1447300300006 and unfiltered measurements from 20 - 600 keV using the1447300300007 FITACS code included in the SAMMY analysis package. 1447300300008 ERR-ANALYS (DATA-ERR) Total uncertainty. 1447300300009 FLAG (1.) Unfiltered neutron beam 1447300300010 (2.) Filterd neutron beam 1447300300011 ENDBIB 9 0 1447300300012 COMMON 2 3 1447300300013 EN-RES-MIN EN-RES-MAX 1447300300014 KEV KEV 1447300300015 20. 600. 1447300300016 ENDCOMMON 3 0 1447300300017 DATA 4 6 1447300300018 MOMENTUM L DATA DATA-ERR FLAG 1447300300019 NO-DIM NO-DIM NO-DIM NO-DIM 1447300300020 0. 1.71E-4 0.12E-4 1. 1447300300021 0. 1.70E-4 0.12E-4 2. 1447300300022 1. 0.52E-4 0.10E-4 1. 1447300300023 1. 0.53E-4 0.09E-4 2. 1447300300024 2. 2.60E-4 0.60E-4 1. 1447300300025 2. 2.45E-4 0.56E-4 2. 1447300300026 ENDDATA 8 0 1447300300027 ENDSUBENT 26 0 1447300399999 SUBENT 14473004 20171129 14331447300400001 BIB 5 9 1447300400002 REACTION (73-TA-181(N,G),,WID,,AV) 1447300400003 STATUS (TABLE) Data taken from tab. 6 of the reference 1447300400004 (DEP,14473002) 1447300400005 ANALYSIS Average resonance parameters were fit to both filtered 1447300400006 and unfiltered measurements from 20 - 600 keV using the1447300400007 FITACS code included in the SAMMY analysis package. 1447300400008 ERR-ANALYS (DATA-ERR) Total uncertainty. 1447300400009 FLAG (1.) Unfiltered neutron beam 1447300400010 (2.) Filterd neutron beam 1447300400011 ENDBIB 9 0 1447300400012 COMMON 2 3 1447300400013 EN-RES-MIN EN-RES-MAX 1447300400014 KEV KEV 1447300400015 20. 600. 1447300400016 ENDCOMMON 3 0 1447300400017 DATA 4 6 1447300400018 MOMENTUM L DATA DATA-ERR FLAG 1447300400019 NO-DIM MILLI-EV MILLI-EV NO-DIM 1447300400020 0. 62.6 5.1 1. 1447300400021 0. 63.4 5.3 2. 1447300400022 1. 55.0 13.1 1. 1447300400023 1. 52.9 13.5 2. 1447300400024 2. 60.5 1. 1447300400025 2. 60.5 2. 1447300400026 ENDDATA 8 0 1447300400027 ENDSUBENT 26 0 1447300499999 ENDENTRY 4 0 1447399999999